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KR920003331A - How to protect your reactor if the load increases - Google Patents

How to protect your reactor if the load increases Download PDF

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Publication number
KR920003331A
KR920003331A KR1019910012138A KR910012138A KR920003331A KR 920003331 A KR920003331 A KR 920003331A KR 1019910012138 A KR1019910012138 A KR 1019910012138A KR 910012138 A KR910012138 A KR 910012138A KR 920003331 A KR920003331 A KR 920003331A
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South Korea
Prior art keywords
reactor
emergency stop
operating temperature
temperature
core
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KR1019910012138A
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KR100237114B1 (en
Inventor
모아레바 쟝-루시엥
파바제 올리브예
코커롤스 삐에르
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비셀 달사세
프라마톰
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/08Regulation of any parameters in the plant
    • G21D3/10Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

내용 없음No content

Description

부하가 증가하는 경우의 원자로 보호 방법How to protect your reactor if the load increases

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음As this is a public information case, the full text was not included.

제1도는 본 발명이 적용되는 원자로의 다이아그램,1 is a diagram of a nuclear reactor to which the present invention is applied,

제4도는 제1도의 원자로에 적용가능한 본 발명의 과출력 시스템의 흐름도.4 is a flow chart of the overpower system of the present invention applicable to the reactor of FIG.

Claims (6)

원자력(DT)이 비상정지 한계(LP)에 도달하는 경우에 원자로의 비상 정지가 시동되도록, 원자로의 부하가 증가하는 경우 원자로 특히, 가압수형 원자로를 보호하는 방법에 있어서, 상기 비상 정지 한계는 원자로의 낮은 작동 온도(ST)에서 낮아지는 것을 특징으로 하는 원자로 보호방법.In a method of protecting a reactor, in particular a pressurized water reactor, when the load of the reactor increases, such that the emergency stop of the reactor is started when nuclear power (DT) reaches the emergency stop limit (LP), the emergency stop limit is a reactor. Reactor protection method characterized in that the lower at a lower operating temperature (ST). 제1항에 있어서, 상기 원자로는, 원자핵 반응이 일어나는 연료봉들을 내장하고, 노심의 상부와 하부사이에 분포되어 열로 전환되는 원자력을 발생시키는 노심(2)와, 열 교환 유체가 노심을 통해 흐르게하고 배출덕트(6)을 경유하여 노심을 떠나게 하기 위해 인입 덕트(4)를 경유하여 노심속으로 관통하게 함으로써 상기 열을 제거하여 그 열을 변하는 수요을 갖는 열 수납기(10)으로 전달하는 열 교환 회로(4, 6, 8)과, 상기 원자핵 반응을 제어하기 위해 상부로부터 상기 코어속으로 제어된 방식으로 관통하는 제어용 클러스터(12)와, 상기 원자력을 나타내는 총 출력 신호(DT)를 전달하는 적어도 하나의 출력 측정 시스템(14)와, 상기 열 교환 유체의 온도인 작동 온도를 나타내는 작동 온도 신호(ST)를 제공하는 온도 측정 시스템(18)과, 적어도 대략 수요에 상당하는 화력을 상기 열 수납기가 받도록 특히 상기 열수납기(10)의 수용의 변화의 함수로서 상기 제어봉 클러스터(12)의 일부에 작용하는 출력 제어 시스템(24)와, 상기 원자핵 반응을 신속하게 정지시키기 위해 상기 제어봉 집단을 상기 노심속으로 관통시키는 비상 정지 신호를 전달할 수 있고 그러기 위해서 적어도 상기 총 출력 신호 및 상기 작동온도 신호를 받아서 상기 총 출력 신호(ET)로 나타낸 원자력이 적어도 상기 온도 신호(ST)에 기초하여 한정된 비상 정지 한계(LP)를 초과할 때 상기 비상 정지 신호(AR)을 전달하는 과출력 보호 시스템(30)을 구비하고, 상기 비상 정지 한계(LP)는 기준 온도(TR) 이하인 작동 온도(T)에 상당하는 상기 온도 신호(ST)값에서 낮아지는 것을 특징으로 하는 원자로 보호방법.The reactor according to claim 1, wherein the reactor includes a core (2) for embedding fuel rods in which a nuclear reaction occurs, generating a nuclear power distributed between the upper and lower portions of the core and converting it into heat, and allowing a heat exchange fluid to flow through the core; A heat exchange circuit that removes the heat by passing it through the inlet duct 4 through the inlet duct 4 to leave the core via the discharge duct 6 and transfers the heat to the heat receiver 10 having a varying demand ( 4, 6, 8), a control cluster 12 penetrating in a controlled manner from the top into the core to control the nuclear reaction, and at least one transmitting a total output signal DT representing the nuclear power. An output measuring system 14, a temperature measuring system 18 for providing an operating temperature signal ST indicating an operating temperature which is the temperature of the heat exchange fluid, and at least approximately equivalent to the demand An output control system 24 acting on a portion of the control rod cluster 12 as a function of a change in the accommodation of the heat receiver 10 so that thermal power is received by the heat receiver, and in order to quickly stop the nuclear reaction It is possible to transmit an emergency stop signal that penetrates the control rod population into the core so that at least the total output signal and the operating temperature signal are received and the nuclear power represented by the total output signal ET is based on at least the temperature signal ST. And an overpower protection system 30 which transmits the emergency stop signal AR when the defined emergency stop limit LP is exceeded, the emergency stop limit LP being an operating temperature below the reference temperature TR. Reactor protection method characterized in that the lowering in the temperature signal (ST) value corresponding to T). 제2항에 있어서, 상기 비상 정지 한계(LP)는 상기 작동 온도(ST)의 함수로서 양의 기울기 법칙을 따르는 것을 특징으로 하는 원자로 보호 방법.3. A method according to claim 2, wherein the emergency stop limit (LP) follows a positive slope law as a function of the operating temperature (ST). 제3항에 있어서, 상기 비상 정지 한계(LP)에 적용 가능한 상기 양의 기울기 법칙은 직선형 법칙인 것을 특징으로 하는 원자로 보호 방법.4. The method of claim 3, wherein the positive slope law applicable to the emergency stop limit (LP) is a linear law. 제2항에 있어서, 상기 기준 온도(TR)은 270℃ 내지 320℃의 범위에 있고, 상기 방법이 가압수형 원자로에 적용될 때 바람직하게는 290℃ 내지 300℃의 범위에 있는 것을 특징으로 하는 원자로 보호방법.The reactor protection according to claim 2, wherein the reference temperature (TR) is in the range of 270 ° C to 320 ° C and is preferably in the range of 290 ° C to 300 ° C when the method is applied to a pressurized water reactor. Way. 제5항에 있어서, 상기 작동 온도(ST)는 상기 기준 온도(TR)보다 20℃ 낮고, 상기 비상 정지 한계(LP)는 상기 작동 온도가 상기 기준 온도보다 더 클때 갖는 값의 1/2보다 낮은 값을 갖는 것을 특징으로 하는 원자로 보호방법.The method according to claim 5, wherein the operating temperature (ST) is 20 ° C lower than the reference temperature (TR), and the emergency stop limit (LP) is lower than half of the value having when the operating temperature is greater than the reference temperature Reactor protection method characterized in that it has a value. ※ 참고사항 : 최초출원 내용에 의하여 공개되는 것임.※ Note: This is to be disclosed by the original application.
KR1019910012138A 1990-07-17 1991-07-16 How to protect your reactor if the load increases Expired - Lifetime KR100237114B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR9009094 1990-07-17
FR9009094A FR2665013B1 (en) 1990-07-17 1990-07-17 PROCESS FOR PROTECTING A NUCLEAR REACTOR IN THE EVENT OF A LOAD RISE.

Publications (2)

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KR920003331A true KR920003331A (en) 1992-02-29
KR100237114B1 KR100237114B1 (en) 2000-01-15

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US (1) US5169592A (en)
EP (1) EP0467787B1 (en)
JP (1) JPH0511092A (en)
KR (1) KR100237114B1 (en)
CN (1) CN1058286A (en)
DE (1) DE69105386T2 (en)
ES (1) ES2064949T3 (en)
FR (1) FR2665013B1 (en)
ZA (1) ZA915585B (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5309485A (en) * 1992-07-06 1994-05-03 General Electric Company Core automated monitoring system
US5528639A (en) * 1994-08-01 1996-06-18 General Electric Company Enhanced transient overpower protection system
CN106887265B (en) * 2017-03-14 2018-05-15 国核电力规划设计研究院有限公司 The start and stop shut-down system of one bulb bed modular high temperature gas cooled reactor

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3979255A (en) * 1973-09-04 1976-09-07 Combustion Engineering, Inc. Method for operating a system with a variable excursion margin setpoint
JPS5552998A (en) * 1978-10-16 1980-04-17 Hitachi Ltd Reactor recirculation flow rate control device
US4308099A (en) * 1979-01-22 1981-12-29 The Babcock & Wilcox Company Nuclear reactor safety system
FR2542493B1 (en) * 1983-03-11 1985-12-27 Framatome Sa DEVICE FOR QUICK AND ACCURATE DETERMINATION OF THE POWER OF A PRESSURE WATER NUCLEAR REACTOR
JPS59184895A (en) * 1983-04-06 1984-10-20 株式会社日立製作所 Method of controlling reactor load following-up
US4637911A (en) * 1984-07-24 1987-01-20 Massachusetts Institute Of Technology Apparatus and method for closed-loop control of reactor power
JPS629413A (en) * 1985-07-05 1987-01-17 Hitachi Ltd Power plant control equipment
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Also Published As

Publication number Publication date
ES2064949T3 (en) 1995-02-01
JPH0511092A (en) 1993-01-19
US5169592A (en) 1992-12-08
KR100237114B1 (en) 2000-01-15
EP0467787A1 (en) 1992-01-22
FR2665013A1 (en) 1992-01-24
FR2665013B1 (en) 1992-09-18
ZA915585B (en) 1992-04-29
EP0467787B1 (en) 1994-11-30
CN1058286A (en) 1992-01-29
DE69105386T2 (en) 1995-04-20
DE69105386D1 (en) 1995-01-12

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